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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Hyung Kook Joo, Chang Hyo Kim, Jae Man Noh, Si-Hwan Kim
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 300-312
Technical Paper | doi.org/10.13182/NSE94-A18989
Articles are hosted by Taylor and Francis Online.
New core-reflector boundary conditions designed to replace the explicit representation of the reflector in nodal computations are developed taking into account the transverse leakage in the reflector region. Two approximations are introduced for the transverse leakage in the reflector region: exponential approximation for the slab reflector and quadratic polynomial and exponential approximation for the L-shaped reflector. Core-reflector boundary conditions that relate net current with flux at the core-reflector interfaces are then derived by solving the transverse integrated neutron diffusion equation with transverse leakage approximations in the reflector region. To test the usefulness of new core-reflector boundary conditions, nodal expansion method computations with and without explicit representation of reflectors are performed for the core power distribution and criticality of Zion-1 and YGN-1 pressurized water reactors. It is demonstrated that core power and criticality computations with new boundary conditions agree very well with those with the reflector included explicitly in computational nodes.